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Method for loading control rod of supercritical water-cooled reactor and structure

A control rod and supercritical technology, applied in the field of nuclear reactors, can solve problems such as difficulty in applying supercritical water-cooled reactors, and achieve the effects of meeting stability requirements, increasing the number of arrangements, and reducing the number of

Active Publication Date: 2017-03-15
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Therefore, the traditional PWR (pressurized water-cooled reactor) and BWR (boiling water-cooled reactor) control rod assembly layout and operation management methods are difficult to apply to supercritical water-cooled reactors. Under the conditions of the number of components arranged, enhanced core reactivity control capability and operational flexibility, the difficulty and requirements of SCWR pressure vessel structural design are reduced, and the feasibility of SCWR engineering is significantly improved

Method used

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  • Method for loading control rod of supercritical water-cooled reactor and structure
  • Method for loading control rod of supercritical water-cooled reactor and structure
  • Method for loading control rod of supercritical water-cooled reactor and structure

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Embodiment 1

[0043] Such as figure 1 As shown, a supercritical water-cooled reactor control rod loading method selects a single or multiple adjacent control rod assemblies as an assembly, and fixes the control rod assemblies on the assembly to a control rod drive mechanism, The lifting or lowering of single or multiple control rod assemblies on the control rod driving mechanism is completed.

[0044] The invention provides a new design method for the arrangement scheme of the control rod assembly applied to the supercritical water-cooled reactor, that is, single or multiple adjacent control rod assemblies are taken as an assembly and driven by a control rod driving mechanism. Compared with the existing PWR "checkerboard" control rod assembly arrangement method, the number of control rod assembly arrangements can be greatly increased. Compared with the BWR full-core control rod assembly arrangement method, the required number of control rod drive mechanisms can be larger The magnitude is ...

Embodiment 2

[0047] In this embodiment, the method described in Embodiment 1 is further defined or provided with a specific implementation, such as Figure 1 to Figure 18 As shown, as a design scheme to limit the value of a single bundle of control rod assemblies, the number of control rod assemblies on an assembly is not more than five.

[0048] As a specific control rod assembly loading method, the control rod assemblies forming an assembly are all square assembly cores, and the assembly is any one of the following control rod assembly combinations: C1, including a box of control rod assemblies; C2, including two boxes of control rod assemblies, two boxes of control rod assemblies arranged in a row; C3, including three boxes of control rod assemblies, three boxes of control rod assemblies arranged in a row; C4, including four boxes of control rod assemblies, four boxes of control rod assemblies Arranged in a row; C5, including three boxes of control rod assemblies, any side of two boxes ...

Embodiment 3

[0059] In this embodiment, the structure described in Embodiment 1 is further defined or provided with a specific implementation, such as Figure 1 to Figure 18 As shown, as a further limitation to the above loading structure, the number of control rod assemblies on the same control rod drive mechanism is not more than five.

[0060] The control rod assemblies are all square cores, and the arrangement of the control rod assemblies on the same control rod drive mechanism includes any one of the following: C1, including one box of control rod assemblies; C2, including two boxes of control rod assemblies, two Boxes of control rod assemblies arranged in a row; C3, including three boxes of control rod assemblies, three boxes of control rod assemblies arranged in a row; C4, including four boxes of control rod assemblies, four boxes of control rod assemblies arranged in a row; C5, including three boxes of control rod assemblies rod assemblies, any side of the two boxes of control rod...

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Abstract

The invention discloses a method for loading a control rod of a supercritical water-cooled reactor and a structure. The method comprises the following steps: selecting one or more adjacent control rod components as a combined component; fixing the control rod components on the combined component on a control rod driving mechanism; and lifting or downward inserting one or more control rod components by the control rod driving mechanism. The structure comprises the control rod components and the control rod driving mechanism located on a supercritical water-cooled reactor pressure vessel, wherein one or more adjacent control rod components are fixed on the same control rod driving mechanism. According to the invention, the difficulty in designing a top cover of the supercritical water-cooled reactor pressure vessel is reduced, the running management procedure of the control rod components is simplified, and the economical efficiency, safety and engineering realizability of the supercritical water-cooled reactor are promoted.

Description

technical field [0001] The invention relates to the technical field of nuclear reactors, in particular to a supercritical water-cooled reactor control rod loading method and structure. Background technique [0002] Supercritical water-cooled reactor (SCWR) is a high-temperature (outlet temperature above 500°C), high-pressure (system operating pressure 25MPa) reactor, which has outstanding advantages such as high thermal efficiency and simplified system. Since SCWR uses direct circulation and the coolant density is low, only control rod assemblies and solid burnable poisons can be used to control backup reactivity. In order to realize the long-cycle core loading design and improve the reactivity control capability, it is necessary to arrange a large number of control rod assemblies in the stack (more than 90% of the control rod assemblies are arranged) and arrange a corresponding number of control rod drive mechanisms on the top of the stack. This brings great difficulties t...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C7/117G21C7/12
CPCG21C7/117G21C7/12Y02E30/30
Inventor 夏榜样卢迪王连杰李庆李翔
Owner NUCLEAR POWER INSTITUTE OF CHINA
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